Published 2016 | Version v1
Journal article

Tritium Release Limit for Fluoride Salt-cooled High-temperature Reactors

  • 1. Nuclear Engineering Program, Ohio State University, Columbus, OH 43210 (United States)
  • 2. Oak Ridge National Laboratory, Oak Ridge, TN 37831 (United States)
  • 3. Nuclear Engineering Program, University of Idaho, Moscow, ID 83844 (United States)
  • 4. Idaho National Laboratory, Idaho Falls, ID 83402 (United States)

Description

Tritium generation is potentially a significant issue in Fluoride salt-cooled High-temperature Reactors (FHRs). Tritium in its molecular form, T2, is highly permeable through reactor structure materials, especially under high temperatures. Since tritium presents a potential health hazard, its release must be controlled and mitigated. However, tritium release limit for FHRs is not specified in the current radiation protection regulations since FHRs are still being developed. This study first reviews related radiation protection regulations and literature before proposing a potential limit value of the tritium release rate for FHRs. (authors)

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
115
Journal Page Range
p. 1059-1062
ISSN
0003-018X

Conference

Title
2016 ANS Winter Meeting and Nuclear Technology Expo
Dates
6-10 Nov 2016
Place
Las Vegas, NV (United States)

Optional Information

Notes
23 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)